K. N. Toosi University of Technology
Radiation Physics and Engineering
2645-6397
2645-5188
1
1
2020
01
01
Measurement of naturally occurring radioactive materials concentration in Tehran’s water using Gamma spectrometry
1
5
EN
Mehrnaz
Zehtabvar
Department of Nuclear Engineering, Faculty of Engineering, Islamic Azad University, Science and Research Branch, Tehran, Iran.
Dariush
Sardari
Department of Medical Radiation Engineering, Faculty of Engineering, Islamic Azad University, Science and Research Branch, Tehran, Iran.
Gholamreza
Jahanfarnia
Department of Nuclear Engineering, Faculty of Engineering, Islamic Azad University, Science and Research Branch, Tehran, Iran.
10.22034/rpe.2020.57882
The concentration of naturally occurring radioactive materials (NORM) in surface water and irrigation wells is measured using gamma ray spectrometry by HPGe detector. Measurement was carried out for samples that were collected over seventeen points in Tehran city and its suburbs. The samples were prepared in compliance with the principles from irrigation wells of city. The specific radioactivity of Ra-226, Th-232 and K-40 were measured and the results from different locations covered a range with the minimum being below "minimum detectable activity" up to maximum of 4.04, and 6.85 and 4.7 Bq per liter of water, respectively. The accumulation of radioactive materials in the samples from southern areas of Tehran was more than that of central areas. Also, concentration of Ra-226 in all the samples was less than the Derived Release Limit of Canada and Environmental Protection Agency standard threshold.
Naturally radioactive materials,Gamma ray spectrometry,HPGe detector,Tehran's water
https://rpe.kntu.ac.ir/article_57882.html
https://rpe.kntu.ac.ir/article_57882_28456f715939469b56483ca8f76c96b3.pdf
K. N. Toosi University of Technology
Radiation Physics and Engineering
2645-6397
2645-5188
1
1
2020
01
01
Introducing a novel FDG synthesis method in Iran based on alkaline hydrolysis
7
11
EN
Parviz
Ashtari
Application Radiation Research School, Nuclear Science and Technology Research Institute, Tehran, Iran.
10.22034/rpe.2020.57883
18F-FDG PET/CT is commonly used for evaluation and diagnostic of many types of cancer, such as; tumor diagnosis, treatment monitoring, and radiation therapy planning. Accurate diagnostic is needed in meticulous patient preparation, including restrictions of diet and activity and management of blood glucose levels in diabetic patients, as well as an awareness of the effect of medications and environmental conditions. All of these conditions play important roles toward obtaining good-quality images, which are essential for accurate interpretation. This article introduces the new synthesis and quality control method for obtaining the best quality FDG which is used as radiopharmaceutical. All the reactions are carried out and completed in one reaction vessel without any replacement. The paper is including details of synthesis, quality control and transportation step. It is the first time that the alkaline FDG synthesis is introducing by details in Iran.
Alkaline Hydrolysis,Synthesis,FDG=[18F]Fluorodeoxyglucose
https://rpe.kntu.ac.ir/article_57883.html
https://rpe.kntu.ac.ir/article_57883_e9a35a4728a0959ba7c83509d60a1196.pdf
K. N. Toosi University of Technology
Radiation Physics and Engineering
2645-6397
2645-5188
1
1
2020
01
01
A Geant4 study on dosimetric comparison between three kinds of radioactive esophageal stents to be used in treatment of advanced esophageal cancers
13
18
EN
Payam
Rafiepour
Department of Nuclear Engineering and Physics, Amirkabir University of Technology, Tehran, Iran
Shahab
Sheibani
Nuclear Science Research School, Nuclear Science and Technology Research Institute NSTRI, Tehran, Iran
Daryiush
Rezaey Uchbelagh
Department of Nuclear Engineering and Physics, Amirkabir University of Technology, Tehran, Iran
Hossein
Poorbaygi
Nuclear Science Research School, Nuclear Science and Technology Research Institute NSTRI, Tehran, Iran
10.22034/rpe.2020.57884
Utilizing radioactive stents is a usual method for treatment of advanced esophageal cancer. It is necessary to investigate the dose distribution of radioactive esophageal stents before the clinical use. This study presents a dosimetric comparison between three radioactive esophageal stents: I-125 seed-loaded stent, iodine-eluting stent and double-layered iodine-eluting stent. Depth-dose and angular dose distributions were carried out using Geant4 toolkit. Moreover, the effect of interval distance between two adjacent seeds on the dose distribution was investigated. Esophageal stents loaded with I-125 seeds seems to be better than iodine-eluting stents, with the distance less than 15 mm between two adjacent seeds.
Advanced esophageal cancer,Radioactive stent,Brachytherapy,Dosimetry,Geant4
https://rpe.kntu.ac.ir/article_57884.html
https://rpe.kntu.ac.ir/article_57884_1402e5658ec4b5a1e0cc77a993af45dd.pdf
K. N. Toosi University of Technology
Radiation Physics and Engineering
2645-6397
2645-5188
1
1
2020
01
01
Three-dimensional solution of the forward and adjoint neutron diffusion equation using the generalized least squares finite element method
19
27
EN
Farahnaz
Saadatian Derakhshandeh
MASNA engineering company, P.O. Box 1439951113, Tehran, Iran
10.22034/rpe.2020.57885
Numerical solution of the multi-group static forward and adjoint neutron diffusion equation (NDE) using the Finite Elements Method (FEM) is investigated in detail. A finite element approach based on the generalized least squares method is applied for the spatial discretization of the NDE in 3D-XYZ geometry. A computer code called GELES was also developed based on the described methodology covering linear or quadratic tetrahedral elements generated via the mesh generator for an arbitrary shaped system. A number of test cases are also studied to validate the proposed approach. Moreover, to assess the output dependency to the number of elements, a sensitivity analysis is carried out at the end.
Neutron Diffusion Equation,Adjoint Flux,Generalized Least Squares,Finite Element Method
https://rpe.kntu.ac.ir/article_57885.html
https://rpe.kntu.ac.ir/article_57885_71a444fdd987dd8f87e77a18249cbddc.pdf
K. N. Toosi University of Technology
Radiation Physics and Engineering
2645-6397
2645-5188
1
1
2020
01
01
Calculation of dose uniformity ratio in irradiation cell of GC-220 using analytical method based on multipole moment expansion
29
32
EN
Peiman
Rezaeian
Radiation Applications Research School, Nuclear Science and Technology Research Institute, AEOI, PO Box 11365-3486, Tehran, Iran
Vahideh
Ataenia
Radiation Applications Research School, Nuclear Science and Technology Research Institute, AEOI, PO Box 11365-3486, Tehran, Iran
Sepideh
Shafiei
Physics and Accelerators Research School, Nuclear Science and Technology Research Institute, AEOI, PO Box 11365-3486, Tehran, Iran
10.22034/rpe.2020.57886
In this paper, dose uniformity ratio in irradiation cell of GC-220 is specifiedutilizing an analytical method based on the multipole moment expansion. In this method, the values of monople, dipole and quadrupole moments for source arrangements of GC-220 are calculated by numerical integrating. Appling these values, the dose uniformity ratio in the irradiation cell of GC-220 is calculated equal to 1.92. Monte Carlo simulation is applied to validate calculations. There is a relative difference about 12% between the results obtained from the analytical calculation and Monte Carlo simulation, which confirm the used method. In comparison with Monte Carlo methods, this method is not time consuming, so, this method can be used for the conceptual designing and the source load planning of irradiators.
Dose Uniformity Ratio,Mutipole Moment Expansion,Monte Carlo Method,Gamma Cell 220,Source Load Planning
https://rpe.kntu.ac.ir/article_57886.html
https://rpe.kntu.ac.ir/article_57886_e0e15fa50bd27b21ce8cf778fe89cba4.pdf
K. N. Toosi University of Technology
Radiation Physics and Engineering
2645-6397
2645-5188
1
1
2020
01
01
Reduction of radiation exposure probability at Tehran research reactor equipped with a second shutdown system
33
38
EN
Ehsan
Boustani
Nuclear Science and Technology Research Institute (NSTRI), Reactor and nuclear safety school, Tehran, Iran
Samad
Khakshournia
Nuclear Science and Technology Research Institute (NSTRI), Accelerator and physics school, Tehran 14399-51113, Iran
10.22034/rpe.2020.57887
A second shutdown system (SSS) is designed for the Tehran Research Reactor (TRR) completely independent and diverse from the existing First Shutdown System (FSS). Given limitations, specifications, and requirements of the reactor, the design of SSS is based on the injection of liquid neutron absorber. The plan has the ability to satisfy the major criterion of required negative reactivity worth, to transfer the reactor to subcritical state in needed time, with necessary shutdown margin and for the required duration. Design calculations are performed using the stochastic code MCNPX2.6.0, deterministic code PARET and Pipe Flow Expert software. The ORIGEN2 code and HotSpot health physics code are also used for simulation of environmental pollution release. The SSS chambers cause a decrease of about 5% and 15% in total and thermal neutron flux, respectively. To demonstrate the SSS role in enhancing reactor safety, the probable accident of core meltdown is investigated. As a consequence of this accident, the radioactive pollution in and out of reactor containment is released. Without existing the SSS and in case of failure of FSS, the residents within 58000 m<sup>2</sup> of the reactor perimeter would receive about 1 mSv which is more than the annual limit of absorbed dose for the community.
Tehran research reactor,Safety,Second shutdown system,MCNPX code,ORIGEN2 code,PARET code,HotSpot code
https://rpe.kntu.ac.ir/article_57887.html
https://rpe.kntu.ac.ir/article_57887_06b31557b8cac998728cfa370544f9d2.pdf